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Author: American Nuclear Society. Topical Meeting
Publisher:
ISBN:
Category : Nuclear engineering
Languages : en
Pages : 480
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Book Description
Author: American Nuclear Society. Topical Meeting
Publisher:
ISBN:
Category : Nuclear engineering
Languages : en
Pages : 480
Get Book Here
Book Description
Author: American Nuclear Society. Topical Meeting
Publisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 476
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Book Description
Author: American Nuclear Society
Publisher:
ISBN:
Category :
Languages : en
Pages :
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Book Description
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :
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Book Description
Author: American Nuclear Society
Publisher:
ISBN:
Category :
Languages : en
Pages : 457
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Book Description
Author: Tetsuaki Takeda
Publisher: Academic Press
ISBN: 012821032X
Category : Business & Economics
Languages : en
Pages : 478
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Book Description
High-Temperature Gas Reactors is the fifth volume in the JSME Series on Thermal and Nuclear Power Generation. Series Editor Yasuo Koizumi and his Volume editors Tetsuaki Takeda and Yoshiyuki Inagaki present the latest research on High-Temperature Gas Reactor (HTGR) development and utilization, beginning with an analysis of the history of HTGRs. A detailed analysis of HTGR design features, including reactor core design, cooling tower design, pressure vessel design, I&C factors and safety design, provides readers with a solid understanding of how to develop efficient and safe HTGR within a nuclear power plant. The authors combine their knowledge to present a guide on the safety of HTGRs throughout the entire reactor system, drawing on their unique experience to pass on lessons learned and best practices to support professionals and researchers in their design and operation of these advanced reactor types. Case studies of critical testing carried out by the authors provide the reader with firsthand information on how to conduct tests safely and effectively and an understanding of which responses are required in unexpected incidents to achieve their research objectives. An analysis of technologies and systems in development and testing stages offer the reader a look to the future of HTGRs and help to direct and inform their further research in heat transfer, fluid-dynamics, fuel options and advanced reactor facility selection. This volume is of interest for nuclear and thermal energy engineers and researchers focusing on HTGRs, HTGR plant designers and operators, regulators, post graduate students of nuclear engineering, national labs, government officials and agencies in power and energy policy and regulations. Written by the leaders and pioneers in nuclear research at the Japanese Society of Mechanical Engineers and draws upon their combined wealth of knowledge and experience Includes real examples and case studies from Japan, the US and Europe to provide a deeper learning opportunity with practical benefits Considers the societal impact and sustainability concerns and goals throughout the discussion Includes safety factors and considerations, as well as unique results from performance testing of HTGR systems.
Author: IAEA
Publisher: International Atomic Energy Agency
ISBN: 9201076223
Category : Technology & Engineering
Languages : en
Pages : 87
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Book Description
The reactor core is the central part of a nuclear reactor where nuclear fission occurs. It consists of four basic systems and components: the fuel (including fuel rods and the fuel assembly structure), the coolant, the moderator and the control rods, as well as additional structures such as reactor pressure vessel internals, core support plates, and the lower and upper internal structure in light water reactors. This Safety Guide provides recommendations on meeting the safety requirements established in IAEA Safety Standards Series No. SSR-2/1 (Rev. 1), Safety of Nuclear Power Plants: Design, applied to the design of the reactor core for nuclear power plants. The publication addresses the safety aspects of the core design and includes neutronic, thermohydraulic, thermomechanical and structural mechanical aspects. Other aspects considered are those relating to reactor core control, shutdown and monitoring, and core management.
Author: Gareth B Neighbour
Publisher: Royal Society of Chemistry
ISBN: 1847559999
Category : Science
Languages : en
Pages : 273
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Book Description
Nuclear power currently contributes some 20% of the electricity needs of the UK and is rising rapidly on the political agenda due to environmental and economic factors, and yet all but one of the UK's existing nuclear reactors is expected to close by 2023. The increasing emphasis towards nuclear power rests on security of supply and reducing carbon emissions. This comprehensive book provides an account of the recent advances in securing safe performance of graphite-moderated nuclear reactors both within the UK and abroad which underpin life extension whilst maintaining high levels of plant performance. These reactors rely on graphite as a moderator in the form of layers of interlocked graphite bricks which undergo complex changes when exposed over long periods to the effects of neutron irradiation and radiolytic oxidation. The objective of this book is to outline the current approaches in terms of assessment methodologies, surveillance and test methods, performance prediction, graphite reactor decommissioning, regulatory requirements and the relevance to future reactor designs. The book is a sequel to the successful RSC publication "Managing of Ageing Processes in Graphite Reactor Cores", but with the emphasis on the challenges for the future safe performance. It is hoped that the contributed papers will also help in the design, construction, operation and eventual decommissioning of the new generation of graphite-moderated reactors. Papers presented in the book represent contributions from the most eminent specialists in the field and reflect the UK's contribution over the past 50 years to graphite reactor technology that will remain significant for years to come, especially in the development of Generation IV designs. This seminal book is written in a way that takes the reader from fundamental knowledge to reactor operation in a straight forward and understandable manner - ideal for non-specialist as well as a unique reference for the specialist. It is fully illustrated to aid understanding and is relevant to a wide range of readers from policy makers to reactor operators.
Author: Brian R. T. Frost
Publisher: Elsevier
ISBN: 1483155250
Category : Technology & Engineering
Languages : en
Pages : 284
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Book Description
Nuclear Fuel Elements: Design, Fabrication and Performance is concerned with the design, fabrication, and performance of nuclear fuel elements, with emphasis on fast reactor fuel elements. Topics range from fuel types and the irradiation behavior of fuels to cladding and duct materials, fuel element design and modeling, fuel element performance testing and qualification, and the performance of water reactor fuels. Fast reactor fuel elements, research and test reactor fuel elements, and unconventional fuel elements are also covered. This volume consists of 12 chapters and begins with an overview of nuclear reactors and fuel elements, as well as fuel element design and development based on the reactor operator's approach, materials scientist's approach, and interdisciplinary approach. The reader is then introduced to different types of nuclear fuels and their irradiation behavior, considerations for using cladding and duct materials in fuel element design and development, and fuel element design and modeling. The chapters that follow focus on the testing of fuel element performance, experimental techniques and equipment for testing fuel element designs, and the performance of fuels for water reactors. Fuel elements for gas-cooled reactors, fast reactors, and research and test reactors are also described. The book concludes with an assessment of unconventional fuel elements. This book will be useful to fuel element technologists as well as materials scientists and engineers.
Author: David Miller
Publisher:
ISBN:
Category : Nuclear fuel elements
Languages : en
Pages : 106
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Book Description
